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| | number = ML121880617 | | | number = ML121880617 |
| | issue date = 07/06/2012 | | | issue date = 07/06/2012 |
| | title = Callaway Plant, Unit 1 - Request for Additional Information, Round 2, License Amendment Request to Revise Technical Specification 3.3.6, Containment Purge Isolation Instrumentation, to Add a Note to Required Action B.1 (TAC ME7205) | | | title = Request for Additional Information, Round 2, License Amendment Request to Revise Technical Specification 3.3.6, Containment Purge Isolation Instrumentation, to Add a Note to Required Action B.1 |
| | author name = Hon A | | | author name = Hon A |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Elwood T B, Maglio S A | | | addressee name = Elwood T, Maglio S |
| | addressee affiliation = Union Electric Co | | | addressee affiliation = Union Electric Co |
| | docket = 05000483 | | | docket = 05000483 |
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| {{#Wiki_filter:A. Heflin Enclosure 1 REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION LICENSE AMENDMENT REQUEST FOR PROPOSED REVISION TO TECHNICAL SPECIFICATION 3.3.6, "CONTAINMENT PURGE ISOLATION INSTRUMENTATION" CALLAWAY PLANT UNIT 1 (TAC NO. ME7205) | | {{#Wiki_filter:A. Heflin 1 REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION LICENSE AMENDMENT REQUEST FOR PROPOSED REVISION TO TECHNICAL SPECIFICATION 3.3.6, CONTAINMENT PURGE ISOLATION INSTRUMENTATION CALLAWAY PLANT UNIT 1 (TAC NO. ME7205) |
| INTRODUCTION Technical Specification (TS) 3.6.3, "Containment Purge Isolation Instrumentation," contains requirements for containment isolation valves. The requirements are applicable during MODES 1, 2, 3, and 4. Inoperability of one or more containment isolation valves in a containment penetration flow path requires the affected penetration(s) to be isolated by a closed valve(s) in accordance with the applicable Required Action(s) under TS 3.6.3. The Required Actions, however, are modified by Note 1 which allows penetration flow path(s) except for containment shutdown purge valve flow paths may be unisolated intermittently under administrative controls." A similar allowance is also provided in TS 3.9.4, "Containment Penetrations." The licensee stated that a similar allowance was also present in TS 3.3.6 but was subsequently removed. The licensee stated that at the time of removing this allowance from TS 3.3.6, it was not recognized that it would unduly limit the use of administrative controls to unisolate the containment mini-purge supply and exhaust valves during certain operational needs such as the ability to vent the containment in order to maintain containment pressure within its required limits. | | INTRODUCTION Technical Specification (TS) 3.6.3, Containment Purge Isolation Instrumentation, contains requirements for containment isolation valves. The requirements are applicable during MODES 1, 2, 3, and 4. Inoperability of one or more containment isolation valves in a containment penetration flow path requires the affected penetration(s) to be isolated by a closed valve(s) in accordance with the applicable Required Action(s) under TS 3.6.3. The Required Actions, however, are modified by Note 1 which allows penetration flow path(s) except for containment shutdown purge valve flow paths may be unisolated intermittently under administrative controls. A similar allowance is also provided in TS 3.9.4, Containment Penetrations. The licensee stated that a similar allowance was also present in TS 3.3.6 but was subsequently removed. The licensee stated that at the time of removing this allowance from TS 3.3.6, it was not recognized that it would unduly limit the use of administrative controls to unisolate the containment mini-purge supply and exhaust valves during certain operational needs such as the ability to vent the containment in order to maintain containment pressure within its required limits. |
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| The licensing amendment request (LAR) submittal on September 22, 2011 did not include sufficient information on how the limitation has impacted the ability to vent the containment in terms of frequency and duration. In addition, the proposed note provided in TS 3.3.6 is not sufficiently clear as to what other containment isolation instrumentation could be inoperable when the note is exercised. The NRC staff also requires additional information on the proposed administrative controls and the proposed changes to the TS bases. The NRC staff needs the following information to complete the review of this LAR. | | The licensing amendment request (LAR) submittal on September 22, 2011 did not include sufficient information on how the limitation has impacted the ability to vent the containment in terms of frequency and duration. In addition, the proposed note provided in TS 3.3.6 is not sufficiently clear as to what other containment isolation instrumentation could be inoperable when the note is exercised. The NRC staff also requires additional information on the proposed administrative controls and the proposed changes to the TS bases. The NRC staff needs the following information to complete the review of this LAR. |
| RAI #1 Based on the information in Section 3.3, "ITS Conversion" of Attachment 1 to the LAR, the NRC staff understands that the ability to vent the containment in order to maintain containment pressure within the required limits was impacted at Callaway Plant. Unit 1 since 1999. The plant had operated under this limitation imposed by TS 3.3.6 for the past 12 years. The staff would like to have a better understanding of how this limitation has impacted the ability to vent the containment. Please provide additional information about the venting frequency and how often the need to vent containment does actually coincide with action entries related to TS 3.3.6. Also, please clarify if the limitation ever lead to a plant shutdown, and if so, please clarify how many plant shutdowns actually occurred in the period since 1999 that can be attributed to this limitation. | | RAI #1 Based on the information in Section 3.3, ITS Conversion of Attachment 1 to the LAR, the NRC staff understands that the ability to vent the containment in order to maintain containment pressure within the required limits was impacted at Callaway Plant. Unit 1 since 1999. The plant had operated under this limitation imposed by TS 3.3.6 for the past 12 years. The staff would like to have a better understanding of how this limitation has impacted the ability to vent the containment. Please provide additional information about the venting frequency and how often the need to vent containment does actually coincide with action entries related to TS 3.3.6. Also, please clarify if the limitation ever lead to a plant shutdown, and if so, please clarify how many plant shutdowns actually occurred in the period since 1999 that can be attributed to this limitation. |
| RAI #2 A. Heflin Enclosure 2Please describe how often the containment vented and how long the mini-purge system operated during a typical venting event in MODES 1, 2, 3, and 4. | | RAI #2 Enclosure |
| RAI #3 Table 3.3.6-1 of TS 3.3.6 contains a total of four (4) functions related Containment Purge Isolation instrumentation. The NRC staff understands that the request for TS amendment is limited to the inoperability of Function 3 only in TS Table 3.3.6-1. However, the proposed insert TS-1 to TS page 3.3-60 could be understood to mean that amendment can be applied during inoperability of Function 1 also. The discussion provided in the last paragraph of LAR Section 3.5, "Technical Analysis," appears to imply that the mini-purge valves could be opened when both Functions 1 and 3 are inoperable, please clarify if the intent of the proposed note.
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| RAI #4 LAR Insert TSB-1 to the TS bases references the minimum containment pressure analysis for emergency core cooling system (ECCS) performance capability, as described in the FSAR, and the effect of having the containment mini-purge system in operation at the onset of the most limiting case (i.e., a double ended cold leg guillotine break). Please clarify if this a new analysis performed in support of the proposed TS change, or if it is an existing analysis. If it is a new analysis, the NRC staff may need to review it.
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| RAI #5 LAR Insert TSB-2 to the TS bases provides a discussion of administrative controls consisting of a designated control room operator to rapidly close the valves when a need for system isolation is indicated. Please provide additional information on the administrative controls in support of the proposed change including what other means are available for system isolation given that Function 3 isolation instrumentation is inoperable. Please clarify if the administrative controls consist of designating control room operator only or if they include dedicated operator(s) locally at the valves.
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| RAI #6 Please explain if there are any dose calculations or accident evaluations (e.g., design basis accidents or other events evaluated in FSAR) that rely on the functioning of the instrumentation in Function 3 of Table 3.3.6-1 of TS 3.3.6 and, if there are some, provide justification for the proposed change.
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| RAI #7 The proposed change does not appear to be consistent with the corresponding TS 3.6.3, "Containment Isolation Valves," that included the following Note 1 for similar situations: | | A. Heflin 2 Please describe how often the containment vented and how long the mini-purge system operated during a typical venting event in MODES 1, 2, 3, and 4. |
| | RAI #3 Table 3.3.6-1 of TS 3.3.6 contains a total of four (4) functions related Containment Purge Isolation instrumentation. The NRC staff understands that the request for TS amendment is limited to the inoperability of Function 3 only in TS Table 3.3.6-1. However, the proposed insert TS-1 to TS page 3.3-60 could be understood to mean that amendment can be applied during inoperability of Function 1 also. The discussion provided in the last paragraph of LAR Section 3.5, Technical Analysis, appears to imply that the mini-purge valves could be opened when both Functions 1 and 3 are inoperable, please clarify if the intent of the proposed note. |
| | RAI #4 LAR Insert TSB-1 to the TS bases references the minimum containment pressure analysis for emergency core cooling system (ECCS) performance capability, as described in the FSAR, and the effect of having the containment mini-purge system in operation at the onset of the most limiting case (i.e., a double ended cold leg guillotine break). Please clarify if this a new analysis performed in support of the proposed TS change, or if it is an existing analysis. If it is a new analysis, the NRC staff may need to review it. |
| | RAI #5 LAR Insert TSB-2 to the TS bases provides a discussion of administrative controls consisting of a designated control room operator to rapidly close the valves when a need for system isolation is indicated. Please provide additional information on the administrative controls in support of the proposed change including what other means are available for system isolation given that Function 3 isolation instrumentation is inoperable. Please clarify if the administrative controls consist of designating control room operator only or if they include dedicated operator(s) locally at the valves. |
| | RAI #6 Please explain if there are any dose calculations or accident evaluations (e.g., design basis accidents or other events evaluated in FSAR) that rely on the functioning of the instrumentation in Function 3 of Table 3.3.6-1 of TS 3.3.6 and, if there are some, provide justification for the proposed change. |
| | RAI #7 The proposed change does not appear to be consistent with the corresponding TS 3.6.3, Containment Isolation Valves, that included the following Note 1 for similar situations: |
| Penetration flow path(s) except for containment shutdown purge valve flow paths may be unisolated intermittently under administrative controls. | | Penetration flow path(s) except for containment shutdown purge valve flow paths may be unisolated intermittently under administrative controls. |
| Please clarify whether a similar note should be included in the proposed change to TS 3.3.6.}} | | Please clarify whether a similar note should be included in the proposed change to TS 3.3.6. |
| | Enclosure}} |
Letter Sequence RAI |
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MONTHYEARULNRC-05654, Proposed Revision to Technical Specification 3.3.6, Containment Purge Isolation Instrumentation, (License Amendment Request LDCN 09-0040)2011-09-22022 September 2011 Proposed Revision to Technical Specification 3.3.6, Containment Purge Isolation Instrumentation, (License Amendment Request LDCN 09-0040) Project stage: Request ML1129804802011-10-25025 October 2011 Acceptance Review Email, Revise Technical Specification 3.3.6, Containment Purge Isolation Instrumentation. Project stage: Acceptance Review ML1212901802012-05-0808 May 2012 Email, Request for Additional Information, License Amendment Request to Revise Technical Specification 3.3.6, Containment Purge Isolation Instrumentation, to Add a Note to Required Action B.1 Project stage: RAI ML1218806172012-07-0606 July 2012 Request for Additional Information, Round 2, License Amendment Request to Revise Technical Specification 3.3.6, Containment Purge Isolation Instrumentation, to Add a Note to Required Action B.1 Project stage: RAI ML1218806132012-07-0606 July 2012 Email, Request for Additional Information Regarding License Amendment Request for Proposed Revision to Technical Specification 3.3.6, Containment Purge Isolation Instrumentation Project stage: RAI ULNRC-05888, Response to Request for Additional Information Pertaining to Revision of Technical Specification (TS) 3.3.6, Containment Purge Isolation Instrumentation, LDCN 09-00402012-08-0606 August 2012 Response to Request for Additional Information Pertaining to Revision of Technical Specification (TS) 3.3.6, Containment Purge Isolation Instrumentation, LDCN 09-0040 Project stage: Response to RAI ML12318A2092012-12-0707 December 2012 Issuance of Amendment No. 205, Revise Technical Specification 3.3.6, Containment Purge Isolation Instrumentation, to Add a Note to Required Action B.1 Project stage: Approval 2012-12-07
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Category:Request for Additional Information (RAI)
MONTHYEARML24066A1932024-03-0707 March 2024 2024 Callaway Plant Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ML23200A2982023-07-19019 July 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - Final Request for Additional Information (RAI) - Request for Approval of Oqam, Revision 36a - EPID L-2023-LLQ-0000 ML23174A1272023-06-23023 June 2023 Cw FFD Document Request List 2023 ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) ML23163A1572023-06-0606 June 2023 In-service Inspection Request for Information ML23096A0072023-04-0505 April 2023 NRR E-mail Capture - Final Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request to Revise TS 5.5.16 for Permanent Extension of Integrated Leak Rate Testing - EPID L-2022-LLA-0165 ML23080A1382023-03-21021 March 2023 Notification of Inspection (NRC Inspection Report 05000483/2023003) and Request for Information ML23073A0262023-03-13013 March 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - SG Inspection Report Review - EPID L-2022-LRO-0143 ML23037A7092023-02-0606 February 2023 April 2023 Emergency Preparedness Exercise Inspection - Request for Information ML23026A0212023-01-24024 January 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Changes to TS for SFP - ML22287A0952022-10-14014 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22269A4312022-09-26026 September 2022 November 2022 Emergency Preparedness Program Inspection - Request for Information ML22173A0562022-06-22022 June 2022 Information Request, Security IR 2022402 ML22167A0252022-06-15015 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Revision to Radiological Emergency Response Plan Regarding Response & Notification Goals - EPID L-2022-LLA-0024 ML22157A0572022-06-0606 June 2022 Notification of NRC Design Bases Assurance Inspection (Programs) (05000483/2022013) and Request for Information ML22154A0122022-06-0202 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22151A0512022-05-27027 May 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22137A0292022-05-16016 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22096A0232022-04-0505 April 2022 NRR E-mail Capture - Callaway Plant - Final RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to GL 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML21336A6392021-12-0202 December 2021 .05 Sec Doc Request ML21319A0062021-11-30030 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ML21258A0382021-09-14014 September 2021 NRR E-mail Capture - Final - Request for Additional Information - Callaway, Unit 1 - LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors- EPID L-2020-LLA-023 ML21159A2352021-06-17017 June 2021 Notification of NRC Triennial Heat Exchanger/Heat Sink Performance Inspection (05000483/2021003) and Request for Information ML21130A5882021-05-11011 May 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions to Adopt a Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004 02 ML21088A3872021-03-30030 March 2021 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000483/2021002) and Request for Information ML21007A1622021-01-0606 January 2021 NRR E-mail Capture - Final - Request for Additional Information - (COVID-19) Callaway Plant, Unit 1 - Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs - EPID L-2021-LLE-0242 ML20203M3682020-07-21021 July 2020 NRR E-mail Capture - Draft Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request - Revision to Technical Specification (TS) 5.3.1 and Deletion of TS 5.3.1.1 and 5.3.1.2 - EPID L-2020-LLA-0046 ML20162A1882020-06-10010 June 2020 Request for Supporting Information for the Callaway SPRA Audit Review - Draft Supplement ML20280A5442020-03-25025 March 2020 Cwy 2020 PIR Request for Information ML20064B6582020-02-27027 February 2020 Second, Third, and Fourth Request for Information for Callaway Dba Teams Inspection 2020011 ML19317E6332019-11-13013 November 2019 Request for Supporting Information for the Callaway SPRA Audit Review ML19107A5152019-04-11011 April 2019 Cwy 2019410 RFI Cyber Security Gap ML19078A2932019-03-18018 March 2019 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000483/2019010) and Request for Information ML19023A2032019-01-22022 January 2019 Notification of NRC Triennial Heat Sink Performance Inspection (05000483/2019001) and Request for Information ML19009A3442019-01-0909 January 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Callaway Plant Class 1E LAR, L-2018-LLA-0062 ML18355A4882018-12-20020 December 2018 NRR E-mail Capture - Formal Release of RAI Ref: Callaway Plant EAL Changes, L-2018-LLA-0239 ML18331A2052018-11-27027 November 2018 NRR E-mail Capture - Formal Release of RAIs Ref: Callaway Relief Request EPID L-2018-LLR-0051 ML18025B4672018-01-24024 January 2018 NRR E-mail Capture - Request for Extension of Due Date for RAI Response ML17304B1912017-10-31031 October 2017 NRR E-mail Capture - Requests for Additional Information Concerning Callaway License Amendment - Thermal Overload Protection ML17142A1352017-05-19019 May 2017 Notification of NRC Design Bases Assurance Inspection (05000483/2017007) and Initial Request for Information ML17115A0622017-04-25025 April 2017 NRR E-mail Capture - Requests for Additional Information -- Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report CAC MF8463 ML17038A2292017-02-0707 February 2017 NRR E-mail Capture - RAI Formal Release for Callaway SG Tube Inspection Report, MF8474 ML16111B3222016-04-20020 April 2016 Notification of Evaluations of Changes, Tests, and Experiments, and Permanent Plant Modifications Inspection (05000483/2016007) and Request for Information ML15316A1532015-11-12012 November 2015 Request for Additional Information Email, Relief Request 13R-11 (Pressurizer Welds) from Code Case N-460 Requirements, Third 10-Year Inservice Inspection Interval ML15096A0942015-04-0606 April 2015 Notification of Inspection (NRC Inspection Report 05000483/2015003) and Request for Information ML14353A1172014-12-22022 December 2014 Request for Additional Information, Round 3, License Amendment Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML14294A7752014-10-28028 October 2014 Request for Additional Information, Round 2, License Amendment Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML14203A0632014-07-25025 July 2014 Request for Additional Information, Relief Request I3R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Rv ISI Frequency from 10 to 20 Years, Third 10-Year ISI Interval ML14178A8232014-07-0101 July 2014 Request for Additional Information, License Amendment Request to Revise Final Safety Analysis Report- Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ULNRC-06117, Callaway Plant, Unit 1, License Revewal Application, Request for Additional Information (RAI) Set 31 Responses2014-04-24024 April 2014 Callaway Plant, Unit 1, License Revewal Application, Request for Additional Information (RAI) Set 31 Responses 2024-03-07
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A. Heflin 1 REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION LICENSE AMENDMENT REQUEST FOR PROPOSED REVISION TO TECHNICAL SPECIFICATION 3.3.6, CONTAINMENT PURGE ISOLATION INSTRUMENTATION CALLAWAY PLANT UNIT 1 (TAC NO. ME7205)
INTRODUCTION Technical Specification (TS) 3.6.3, Containment Purge Isolation Instrumentation, contains requirements for containment isolation valves. The requirements are applicable during MODES 1, 2, 3, and 4. Inoperability of one or more containment isolation valves in a containment penetration flow path requires the affected penetration(s) to be isolated by a closed valve(s) in accordance with the applicable Required Action(s) under TS 3.6.3. The Required Actions, however, are modified by Note 1 which allows penetration flow path(s) except for containment shutdown purge valve flow paths may be unisolated intermittently under administrative controls. A similar allowance is also provided in TS 3.9.4, Containment Penetrations. The licensee stated that a similar allowance was also present in TS 3.3.6 but was subsequently removed. The licensee stated that at the time of removing this allowance from TS 3.3.6, it was not recognized that it would unduly limit the use of administrative controls to unisolate the containment mini-purge supply and exhaust valves during certain operational needs such as the ability to vent the containment in order to maintain containment pressure within its required limits.
The licensing amendment request (LAR) submittal on September 22, 2011 did not include sufficient information on how the limitation has impacted the ability to vent the containment in terms of frequency and duration. In addition, the proposed note provided in TS 3.3.6 is not sufficiently clear as to what other containment isolation instrumentation could be inoperable when the note is exercised. The NRC staff also requires additional information on the proposed administrative controls and the proposed changes to the TS bases. The NRC staff needs the following information to complete the review of this LAR.
RAI #1 Based on the information in Section 3.3, ITS Conversion of Attachment 1 to the LAR, the NRC staff understands that the ability to vent the containment in order to maintain containment pressure within the required limits was impacted at Callaway Plant. Unit 1 since 1999. The plant had operated under this limitation imposed by TS 3.3.6 for the past 12 years. The staff would like to have a better understanding of how this limitation has impacted the ability to vent the containment. Please provide additional information about the venting frequency and how often the need to vent containment does actually coincide with action entries related to TS 3.3.6. Also, please clarify if the limitation ever lead to a plant shutdown, and if so, please clarify how many plant shutdowns actually occurred in the period since 1999 that can be attributed to this limitation.
RAI #2 Enclosure
A. Heflin 2 Please describe how often the containment vented and how long the mini-purge system operated during a typical venting event in MODES 1, 2, 3, and 4.
RAI #3 Table 3.3.6-1 of TS 3.3.6 contains a total of four (4) functions related Containment Purge Isolation instrumentation. The NRC staff understands that the request for TS amendment is limited to the inoperability of Function 3 only in TS Table 3.3.6-1. However, the proposed insert TS-1 to TS page 3.3-60 could be understood to mean that amendment can be applied during inoperability of Function 1 also. The discussion provided in the last paragraph of LAR Section 3.5, Technical Analysis, appears to imply that the mini-purge valves could be opened when both Functions 1 and 3 are inoperable, please clarify if the intent of the proposed note.
RAI #4 LAR Insert TSB-1 to the TS bases references the minimum containment pressure analysis for emergency core cooling system (ECCS) performance capability, as described in the FSAR, and the effect of having the containment mini-purge system in operation at the onset of the most limiting case (i.e., a double ended cold leg guillotine break). Please clarify if this a new analysis performed in support of the proposed TS change, or if it is an existing analysis. If it is a new analysis, the NRC staff may need to review it.
RAI #5 LAR Insert TSB-2 to the TS bases provides a discussion of administrative controls consisting of a designated control room operator to rapidly close the valves when a need for system isolation is indicated. Please provide additional information on the administrative controls in support of the proposed change including what other means are available for system isolation given that Function 3 isolation instrumentation is inoperable. Please clarify if the administrative controls consist of designating control room operator only or if they include dedicated operator(s) locally at the valves.
RAI #6 Please explain if there are any dose calculations or accident evaluations (e.g., design basis accidents or other events evaluated in FSAR) that rely on the functioning of the instrumentation in Function 3 of Table 3.3.6-1 of TS 3.3.6 and, if there are some, provide justification for the proposed change.
RAI #7 The proposed change does not appear to be consistent with the corresponding TS 3.6.3, Containment Isolation Valves, that included the following Note 1 for similar situations:
Penetration flow path(s) except for containment shutdown purge valve flow paths may be unisolated intermittently under administrative controls.
Please clarify whether a similar note should be included in the proposed change to TS 3.3.6.
Enclosure